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2015 | 60 | 2 | 339-345

Article title

Evaluation of passive autocatalytic recombiners operation efficiency by means of the lumped parameter approach*



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The problem of hydrogen behavior in containment buildings of nuclear reactors belongs to thermal-hydraulic area. Taking into account the size of systems under consideration and, first of all, safety issues, such type of analyses cannot be done by means of full-scale experiments. Therefore, mathematical modeling and numerical simulations are widely used for these purposes. A lumped parameter approach based code HEPCAL has been elaborated in the Institute of Thermal Technology of the Silesian University of Technology for simulations of pressurized water reactor containment transient response. The VVER-440/213 and European pressurised water reactor (EPR) reactors containments are the subjects of analysis within the framework of this paper. Simulations have been realized for the loss-of-coolant accident scenarios with emergency core cooling system failure. These scenarios include core overheating and hydrogen generation. Passive autocatalytic recombiners installed for removal of hydrogen has been taken into account. The operational efficiency of the hydrogen removal system has been evaluated by comparing with an actual hydrogen concentration and flammability limit. This limit has been determined for the three-component mixture of air, steam and hydrogen. Some problems related to the lumped parameter approach application have been also identified.










Physical description


1 - 6 - 2015
12 - 12 - 2014
22 - 6 - 2015
30 - 3 - 2015


  • Institute of Thermal Technology, Division of Heat Transfer and Nuclear Power Engineering, Silesian University of Technology, 22 Konarskiego Str., 44-100 Gliwice, Poland, Tel.: +48 32 237 2416, Fax: +48 32 237 2872


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  • 8. International Atomic Energy Agency. (2004). Status of advanced light water reactor designs. IAEA-TECDOC No. 1391. Vienna: IAEA.
  • 9. Debontride, B. (2006). Design of EPR. In Proceedings on International Conference on Nuclear Power Plants for Poland, 1–2 June 2006 (pp. 10.1-10.11). Warsaw, Poland.
  • 10. AREVA. (2009). Applicability of AREVA NP containment response evaluation methodology to the U.S. EPR™ for large break LOCA analysis. AREVA NP Inc. (Technical Report No. 10299-NP, Revision 1).
  • 11. Kostka, P., Techy, Z., & Sienicki, J. (2002). Hydrogen mixing analyses for a VVER containment. In Proceedings of 10th International Conference on Nuclear Engineering, 14–18 April 2002 (paper ICONE10-22206). Arlington, Virginia, USA.
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  • 13. OECD/NEA. (1999). State-of-the-art report on containment thermalhydraulics and hydrogen distribution. Paris: CSNI.

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